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U.S. Department of Energy
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CSRL-V: an ENDF/B-V 227-Group Cross Section Library for Criticality Safety Studies

Conference ·
OSTI ID:5363057
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  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Union Carbine Nuclear Division
The AMPX system was used to generate a P3 227-neutron-group master cross-section library containing data for all materials in the ENDF/B-V general purpose file. CSRL-V is a data base for the subsequent generation of problem-dependent fine- and/or broad-group cross sections for shipping cask calculations and other criticality safety analyses. The problem-dependent data can be used with codes such as KENO IV, ANISN, XSDRNPM, VENTURE, DOT, MORSE, etc. CSRL-V data can be coupled with photon-production and photon-interaction multigroup data produced with the AMPX system to produce coupled neutron-gamma cross-section libraries. Consideration was given to the resonance structure of prominent nuclei, the thresholds of important reactions, and various fission spectra. Data in the CSRL-V library were checked for first-order consistencies and tested in performance parameter calculations for a series of benchmark critical experiments. The CSRL-V library is available on magnetic tape.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Union Carbine Nuclear Division
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USNRC, Office of Nuclear Material Safety and Safeguards
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
5363057
Report Number(s):
CONF-800607--41
Country of Publication:
United States
Language:
English